The effect of divertor magnetic balance on H-mode performance in DIII-D

Pétrie, T.W.; Greenfield, C. M.; Grobener, R.J.; Hyatt, A.W.; Haye, R.J. La; Leonard, A. W.; Mahdavi, M. A.; Osborne, T.H.; Schaffer, M. J.; Thomas, D. M.; West, W.P.; Allen, Steven L.; Fenstermacher, M.E.; Lasnier, C.J.; Porter, G. D.; Wolf, N. S.; Watkins, J.G.; Rhodes, T. L.

doi:10.1016/s0022-3115(00)00492-x

Cited by 36 publications

(34 citation statements)

References 13 publications

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“…The scaling laws for Equ.7 and Equ.8 were developed for single-null geometries. Recent studies on DIII-D, however, suggest that single-null and double-null λ q || are comparable, at least in H-mode [39].…”

Section: Particle Heating In the Divertorsmentioning

confidence: 93%

“…In fact, the peak heat flux can be equalized only if the DN is biased slightly toward the direction opposite the ∇B ion drift [39]. In this study, we assume that a slight offset from "true" DN balance, such that f ∇B/total = 0.5.…”

Section: Particle Heating In the Divertorsmentioning

confidence: 99%

“…How these poloidal drifts affect asymmetries in divertor heat flux and particle flux [39] or the "enrichment" of radiating impurity ions in double-null (DN) divertors is speculative at the present time. Hence, it is prudent to first examine Figure 35: The poloidal distribution of the average and peak radiative heat fluxes are shown for the "most conservative" case No contribution from the divertor or scrapeoff is assumed, in line with our (very) conservative assumptions.…”

Section: Radiating Mantle Approachmentioning

confidence: 99%

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Physics basis for the advanced tokamak fusion power plant, ARIES-AT

Jardin

Kessel

Mau

et al. 2006

Fusion Engineering and Design

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The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A ≡ R/a = 4.0, an elongation and triangularity of κ = 2.17, δ = 0.84 (evaluated at the separatrix surface), a toroidal beta of β = 9.2% (normalized to the vacuum toroidal field on at the plasma center), which corresponds to a normalized beta of β N ≡ 100 × β/(I P (M A)/a(m)B(T )) = 5.4. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is f BS ≡ I BS /I P = 0.91. This leads to a design with total plasma current I P = 12.8M A, and toroidal field of 11.1T (at the coil edge) and 5.8T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.

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Section: Particle Heating In the Divertorsmentioning

confidence: 93%

Section: Particle Heating In the Divertorsmentioning

confidence: 99%

Section: Radiating Mantle Approachmentioning

confidence: 99%

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Physics basis for the advanced tokamak fusion power plant, ARIES-AT

Jardin

Kessel

Mau

et al. 2006

Fusion Engineering and Design

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“…(8) were developed for single-null (SN) geometries. Recent studies on DIII-D, however, suggest that single-null and double-null (DN) λ q || are comparable, at least in H-mode [48].…”

Section: Calculating Particle Heating In the Divertorsmentioning

confidence: 97%

“…These imply that the ratio of the power flowing into the outboard SOL would be roughly eight times that flowing into the inboard SOL. Experimental data would support these arguments, where, for example, the ratio of the peak heat flux to the outer divertor target(s) to that of the inner divertor target(s) were found to be ≥ 8 for high triangularity, DIII-D DN plasmas [49] [50] f pf r : The power "spillover" into the private flux region has been observed on several tokamaks. For DIII-D, this value is typically 0.10-0.15.…”

Section: Calculating Particle Heating In the Divertorsmentioning

confidence: 99%

Physics Basis for the Advanced Tokamak Fusion Power Plant ARIES-AT

Jardin¹,

Kessel²,

Mau³

et al. 2003

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The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A ≡ R/a = 4.0, an elongation and triangularity of κ = 2.20, δ = 0.90 (evaluated at the separatrix surface), a toroidal beta of β = 9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of β N ≡ 100 × β/(I P (MA)/a(m)B(T )) = 5.4. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is f BS ≡ I BS /I P = 0.91. This leads to a design with total plasma current I P = 12.8 MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.

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Simulation of Edge Plasmas in DIII-D Double-Null Configurations

Rensink

Lasnier

Pétrie

et al. 2002

Contrib. Plasma Phys.

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We present fluid model simulation results for the edge plasma in the DIII‐D tokamak with unbalanced double‐null magnetic configurations, including cross field drifts. Input parame‐ters are typical of low‐power operation in DIII‐D. For high‐recycling the plasma tends to be detached from all divertor plates. Midplane plasma and electric field profiles are relatively insensitive to the magnetic imbalance. Divertor heat flux profiles exhibit sharp peaks due to cross‐field drifts when the ion grad‐B drift direction is away from the x‐point toward the magnetic axis.

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The effect of divertor magnetic balance on H-mode performance in DIII-D

Cited by 36 publications

References 13 publications

Physics basis for the advanced tokamak fusion power plant, ARIES-AT

Physics basis for the advanced tokamak fusion power plant, ARIES-AT

Physics Basis for the Advanced Tokamak Fusion Power Plant ARIES-AT

Simulation of Edge Plasmas in DIII-D Double-Null Configurations

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